Fusion Science and Technology / Volume 51 / Number 3 / April 2007 / Pages 460-475
Technical Paper / Alcator C-Mod Tokamak / dx.doi.org/10.13182/FST07-A1433
We describe some of the engineering solutions required to produce a diverted tokamak capable of operation with a toroidal field of 8 T and plasma currents of up to 2 MA. Some design details of the toroidal field magnet, the ohmic heating magnet, the metal plasma-facing components, the rf heating and current drive systems, and the power and liquid nitrogen cooling systems are discussed. Vacuum, vessel bake, boronization, and wall-cleaning systems are also discussed. Finally, disruption research results from Alcator C-Mod are presented.